Tungsten coating on JET divertor tiles for erosion/deposition studies

Sari Lehto (Corresponding Author), Jari Likonen, J.P. Coad, T. Ahlgren, D.E. Hole, M. Mayer, H. Maier, J. Kolehmainen

Research output: Contribution to journalArticleScientificpeer-review

31 Citations (Scopus)

Abstract

Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 μm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.
Original languageEnglish
Pages (from-to)241-245
Number of pages5
JournalFusion Engineering and Design
Volume66-68
DOIs
Publication statusPublished - 2003
MoE publication typeA1 Journal article-refereed
Event22nd Symposium on Fusion Technology - Helsinki, Finland
Duration: 9 Sep 200213 Sep 2002
Conference number: 22

Fingerprint

Tile
Tungsten
Erosion
Coatings
Thermal cycling
Deuterium
Thermal load
Carbon fibers
Sputtering
Impurities
Composite materials
Temperature

Keywords

  • tungsten coating
  • plasma
  • tungsten
  • erosion
  • deposition
  • divertor tiles
  • divertor
  • JET
  • ITER
  • fusion energy
  • fusion reactors

Cite this

Lehto, S., Likonen, J., Coad, J. P., Ahlgren, T., Hole, D. E., Mayer, M., ... Kolehmainen, J. (2003). Tungsten coating on JET divertor tiles for erosion/deposition studies. Fusion Engineering and Design, 66-68, 241-245. https://doi.org/10.1016/S0920-3796(03)00291-6
Lehto, Sari ; Likonen, Jari ; Coad, J.P. ; Ahlgren, T. ; Hole, D.E. ; Mayer, M. ; Maier, H. ; Kolehmainen, J. / Tungsten coating on JET divertor tiles for erosion/deposition studies. In: Fusion Engineering and Design. 2003 ; Vol. 66-68. pp. 241-245.
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Lehto, S, Likonen, J, Coad, JP, Ahlgren, T, Hole, DE, Mayer, M, Maier, H & Kolehmainen, J 2003, 'Tungsten coating on JET divertor tiles for erosion/deposition studies', Fusion Engineering and Design, vol. 66-68, pp. 241-245. https://doi.org/10.1016/S0920-3796(03)00291-6

Tungsten coating on JET divertor tiles for erosion/deposition studies. / Lehto, Sari (Corresponding Author); Likonen, Jari; Coad, J.P.; Ahlgren, T.; Hole, D.E.; Mayer, M.; Maier, H.; Kolehmainen, J.

In: Fusion Engineering and Design, Vol. 66-68, 2003, p. 241-245.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Tungsten coating on JET divertor tiles for erosion/deposition studies

AU - Lehto, Sari

AU - Likonen, Jari

AU - Coad, J.P.

AU - Ahlgren, T.

AU - Hole, D.E.

AU - Mayer, M.

AU - Maier, H.

AU - Kolehmainen, J.

PY - 2003

Y1 - 2003

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AB - Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 μm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.

KW - tungsten coating

KW - plasma

KW - tungsten

KW - erosion

KW - deposition

KW - divertor tiles

KW - divertor

KW - JET

KW - ITER

KW - fusion energy

KW - fusion reactors

U2 - 10.1016/S0920-3796(03)00291-6

DO - 10.1016/S0920-3796(03)00291-6

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